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Die Behandlung der Nachzerfallswärme im Reaktordynamikprogramm TINTE

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1993
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Jülich : Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag, Berichte des Forschungszentrums Jülich 2791, VII, 29 p. ()

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Report No.: Juel-2791

Abstract: The TINTE code system deals with the nuclear and the thermal transient behaviour of the primary circuit of an 1-lTGR tatting into consideration the mutual feedback effects in two-dimensional r-z-geometry. In this paper an update of the treatment of delayed heat production is presented. It is based on the german norm DIN 15485, the rules ofwhich had to be adjusted for use in a dynamics code. For the description of the fuel element power history a substitutehistogram has been constructed from local burnup and optionally from information about shuffling of the fuel bails. As an example the depressurisation accident of a MODUL-1-ITR is calculated. The results obtained are very similar to others previously reported.


Contributing Institute(s):
  1. Publikationen vor 2000 (PRE-2000)
Research Program(s):
  1. 899 - ohne Topic (POF3-899) (POF3-899)

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 Record created 2016-11-09, last modified 2021-01-29


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